ML19338F651

Amend 3 to License DPR-75,deleting Requirement for Util to Plug Certain Tubes in Steam Generators Prior to Exceeding 5% Power

ML19338F651
Person / Time
Site:	Salem
Issue date:	10/10/1980
From:	Miraglia F Office of Nuclear Reactor Regulation
To:
Shared Package
ML19338F652	List: ML19338F651 ML19338F653 ML19338F654
References
NUDOCS 8010270014
Download: ML19338F651 (12)

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PUBLIC SERVICE ELECTRIC AND GAS COMPANY-Th PHl.ADE.PCA E'.EUIK:C CwrANY 1

2 DELMI NA 'UfiR AW.Il iMT CwrARY (j/[

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h DOCKET NO. 50-311-SALEM' NUCLEAR GENERATING STATION. UNITS NO. 2

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-AMENDMENT-TO FACILITY OPERATING' LICENSE Amendment No.~3 f:

License No. DPR-75 1.

TheNuclearRegulatoryCosmission(theCosmission)hasfoundthat:

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A..

The two applications for anendment by Public Service Electric and Gas

' Company, Philadelphia Electric Company Delmarva Power and Light Company and Atlantic City Electric Company (tne licensees) dated i,

August 22, 1980 comply with the standards and requirements of. the

-Cosmission's regulations set forth in 10 CFR Chapter I; l~

B.

The facility will' operate in confdrmity with the applications,'the provisions of the Act, and the regulations of the.Conmission; 5

a C.

There is reasonable assurance-(1) tnat the activities authorized by y

'this amendment can be conducted without endar.gering the. health and i

safety:of the public, and'(11) that such activities will be conducted '

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.in compliance with the Commission's regula+1ons; J

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D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and r

E.

'Thislissuance of this. amendment is in accordance with 10 CFR Part 51 of the Cosmission'.s regulations and all applicable requirements have been satisfied.

2.

Accordingly, the licens'e is-amended by changes to the Technical Specifications as indicated in the attachment 17 this license emendment.

and paragraph 2.C(2) of Facility Operating Lit nse No. DPR-75 is hereby amended to read as follows:

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' ;;(2)-! Technical Specifications?

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The.TbnicalSpecificationsLeontained'in'~AppendicesAandI,as-

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revised thrchgh Ameenteent No. 3 t..are hereby incorporated in ti.e -

license. 0 Public Service Electric and Gas Company:shall. opera' e the'

<x facility lin:accordance with:the Technical Specifications.'

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.This-license ~ amendment; s effective at of the_ date of its: issuance..

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FOR THE NUCLEAR REGULATORY.COM ISSION,

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Frank J. Miraglia Acting inf:

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. Division of. Licensing

Attachment:

Changes to-the Technical

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s. 4 Specifications.

-Date of, Issuance: OCT 101909

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- ATTACitlENTLTO ' LICENSE AMENDENT NO. 3 -

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' FACILITY OPERATING' LICENSE NO. DPR-75 m

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LRevise Appendix A as followsi F-..

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- Remove Pages- ~

Insert Pages

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,, v _ x+ ~ ..s -TAGLE 6.2-1 7% y ~~. s 5-7' - JMINIORM SHIFT CREW COMP 05ITIO/. ~ . x L ~ ' Condition of Unite 2:--No Fuel in Unit il .,,s F e, ir e '4__b s

APPLICA8tE M00ES~

t LICENSE CATEGORY-1, 2, 3 & 4 5&6-2 F 50k i -0L~ 2 1 1 ~Non-Licensed._ 2 1 ICondition of Unit 2 - Unit 1 in M00ES 1, 2, 3 or 4 q .4 4 s APPLICABLE MODES LICENSE CATEGORY 1, 2, 3.S.4 5 &.6 q --. 50L**- 2 2*~ OL" 4-3*** Non Licensed 4 -3~ 2

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Condition of Unit 2 - Unit 1 in M30ES 5 or 6 4 I -APPLICABLE M00ES ELICENSE CATEGORY 1, 2,'3 & 4 5&6 en .'50(**

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• Doss' not include?the : licensed Sedor~ Reactor [0peratori supervising C0ilE:

E i > +: - e ' . m s , 5 ALTERATIONS'..- u n. @3

4,**EacFunitsillbe? super'isedby'ashift(supervisonwho;is.a.1_icensedSR01 -

e m v ~ 'on that! unit;1or~by afsingle individualii_f he is: licensed on both; units. .The second-senior. operator = licensed.for1each unitEmust'be stationed'ini , sthe contro1Lroom area at 'allitimes:when the unit issin operating'.mo. des lc m through;4; and could also:bela single individual if helis licensed on: w cunits l'and 21 ~ 2 ~ .t ~... '***A.re' actor operator:licensediforfeach unit must'be at'the! controls'offthat; ~ $ times when fuel is in the reactor. :Alsofa relief reactor ~ W. ~ ' unit ~at~ al(icensed for. each: unit must be available'.on-shift.

operator l This could

'~' . be a single individua1Jif he/.J. s licensed;for bothtunits.. J y e JShiftcrewcomposition'may;b'e-lessthanithe'ainimuezrequirementsfora . per od of-time not toiexceed-2 hours in~ order to accomodate unexpected i absence of on-duty shift crew members provided:immediate action:is'taken-7- to restore'thefshift crew composition.tofwithin the minimum requirements 4 . of Table 16. 2-1.. <. ~ 'Y f}/}'*. -- 1 / ~ [ s h [ 3 t 7 [..

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,r; c f AgnarSTRATIVE CONTROL 5 ,b e - . ~ ^k j r,,. N :6.3' FACILITY STAFF QUALIFICATIONS x N', s. '4 ~ K6.3.1 ?Each member of.the facility 1staffLshal.1?meetior exceed the minimum : 2 Radiation Protection Engineestwho. shall meet or _eIceed Ee. except for.the 7;gualifications of ANSI N18.1-1971Lfor comparable' siti s (qualifications of Regulatory Guide 11!8 7.5eptember7.1975.i . _ =.

-6)4 TRAINING.

u: y . 6.4.~ 1 ' ? A. retrai,. ility staff .shall'be;coordining and. replacement training program for;the facnated by tho' Assistant 1to = direction of,the Training Engineer and shallineet or exceed the requirements z,'and recommendations of Section.5.5 of ANSI N18.1-1971-and Appendix "A" of g 110 CFR Part 55.' .'k k : 6. 5 REVIEW AND AUDIT. C '6 5.1 ' STATION OPERATIONS REVIEW C0fetITTEE-(50RCF D

FUNCTION, J6;5.1.1;~The~ Station Operations-Review Cosmittee shall functis'

,o advise the f$tation_ Manager on all matters related to' nuclear safety. C0fr051TIONf, m '6.5.1.2 L The Station Operations-Review Committee shall be composed of the:. Chairman..

Chief. Engineer-

' Vice Chairman: . Assistant to Manager Member:. . Station.0perating Engineer. Member:. Station Performance Engineer ~ Member: . Reactor Engineer. Member:,

l. Senior Shift Supervisor..

Member:- ~ Senior Performance Supervisor .-I&C F. Member: Senior Performance Supervisor-Chemistry Member::

Radiation Protection' Engineer l^

Member: - Senior Maintenance.:bupervicor s _ Member:-- , Maintenance Engi.neer: ' iALTERNATES - c 6.5.1.3E All alternate members shall be: appointed in writing by the 50RC. Chaitinen to serve'on.a' temporary basis; /however, no more than two alternatas 1-- . w shall participate.as' voting members in 50RC activities'at'any one time. .] .~ n , [ ETING FREQUENCY see-1. 4 _ 65.1.4L JThe 50RC shell meet ~~at least once; per calendar month. and as convened 2 . W the SOAC Chairman or his: designated alternate. mg-r ,,f q;. W SALBI C WIIT 2' 6-6 M NOMENT N0. 3 N n !4 ~ l H 'f .w

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bInadditifonitolthe:applicablerecoidretentionrequirementsLofTit1e10,. Code- ] w';of. Federal Regulations, the.following records shal1~be retained for at least', j v .the miniopt y lod: indicated.-- 4 D f~ ^ b 16.10.cEThelfollowingrecords(shal10be' retained ^; fora'tleastfive' years: a ~ 4. ..)=

a. IRecords andslsgs'of snit; operation covering time' interval-at each

power level.-

.b. (Recordsandl1ogs-ofprincipalmaintenanceactivities, inspections, repair and rep 1acement of principal' items of equipment related.to lp; -(nuclasesafety.D 1 c.. All REPORTABLE OCCURRENCES' submitted to the Commission. d. Records.of surveillance a::tivities, inspections and calibra'tions . required byfthese Technical -Specifications. .c Records of reactor tests and experiments.

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f.. l Records.of changes made to;.0perating Procedures required by Specifi - i cation;6.8.1.i ' t' g.: Records!ofradicactiveshipments. h'. - Records of' sealed source and fission detector'Itak tests and results. -l 1. Records'ef annuar physical inventory of all sealed source' material ~ of record ~ ~ m [~ (: e 2 6.10.2 EThe following records:shall'be retained for the duration of the Unit- ? Operating Licenre: ~ v a.. - Records;and drawing changes reflecting unit design modifications made:to. systems'and equipment' described in the F<nal Safety Analysis [ . Report. ~ ~~ d ' RecArd61.-'of 'nes and irradiated -fuel inventory, fuel transfers and d b. assambly burnup histories.- - c., Records-.of radiation exposure for all individuals entering' radiation

control areas.

~ pe 4 q ~ m + d. Records of.gessous and liquid radioactive ~ material released to the ~ Hl ' environs.', ^ 1 C SALBI M ITi2-p > >;.: ..6-17 R q i s

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inents identiffed in Table 5.7-1..

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$N ~ L f.s iRecords'ofreactor\\testsandexperiments. - 'b ~ 1g7 1RecordsTof training and. qualification'for current' members of dg plant _ staff.: q 2 i a. h. Records:of in-service inspections, performed pursuant to thew fec b

nical' Specifications..

f-u 1. Records _of quality Assurance activities required by the QA'Ms . il.. j.: Records.of__ reviews performed for changes made to procedures ~ ment or-revleus,of; tests and experiments pursuant to-10 CFR g j; j. g p k. Records of meetings of the 50RC and the NRB. L u.-. .y ~ 5.17 RADIATION PROTECTION PROGRAM 5 - Procedures for personnel radiation protection shall be. prepared consistent. . ith the requirements of.10 CFP Part 20 and shall be approved, maintainedLand w adhered to for all _perations involving personnel radiation exposure. o n E 6.12 HIGH RADIATION AREA ~ a ~

5.12.1 In lieu of the " control device" or " alarm signal". required by paragraph

~~ -20.203(c)(2) of;10 CFR Part 20, each high radiation area in which the intensity _. 'ef radiation is greater than 100 mrom/hr but less than 1000_aren/hr shall-be. -barricaded'and conspicuously posted as a High Radiation Area and entrance. thereto shall be controlled by; issuance of a Radiation Exposure Pemit*. Any individual or group'of individuals permitted to enter such areas shall be i ~ provided with or accespanied by~one or morA of the following: ((. a. .A radiation monitoring.' device which continuously indicates the 2 radiation dose rate in the area. v. l b. A radiation' monitoring device which continuously integrates-the radiation dese' rate in the~ area and alarms when a preset integrated dose'is received.1 Entry into such areas with this monitoring device .may be made after the dose rate level.in the area has been estab-o -p 11shed and personnel have been made knowledgeable of tM a. e v c u ,h'itadiktion. Protection brsonnel;or personnet escorted by. Radiation P shal be exempt frem REP issuance requirement during,tne perfemance of-' {their.' assigned radiation protection duties, provided they comply with ~ < approved radiation: protection procedures for entry into'high raoiation areas. pfw $ALBI - 4RIIT(2 : 6-18. AMEN 0 MENT N0. 3' 3y seg o

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5 equipped with airadiation dose: rate monitoring: device. This'indi-j a -(vidual:sha11:beTresponsible'for.providing positive control: oiter the' V'l -activities within thefarearand'shall; perform periodic radiation m 4 surveillance ~atithe: frequency specified bylthe Senior & Supervisor -- g G"

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4 ~ 4, ~. '6.12.2.lThe' reekirements of 6.12.1," aboves:shall.also apply. to each high' ... E d . 15.: 11ll- ' (radiation area inLwhich the intenAity of radiation)is greater thanL1000 ares /hr.'. In addition,-: locked doors 7sha11Lbe(provided to prevent,unauthorizet entry into 1 ~. such areas:and;the keys:shall be maintained.under the administrative control' s Tof the. Senior Shift SupervisorJon duty'and/or:the Senior Supervisor 5 Radiation - .. l2 n" Protection.1' ~ i I q f .} s 3 ). 4 E-m a >; 4.~ r f: .r. <4 f g[.y ^ ly p. m +Kg -- a

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r5 , pr -g ,y v=mlm%.. x-g6 l-j W Q f. -} j;h~ 3 7 }} [ >l ~ ^ ' yf L. ~ q 6.' y g w u / L8.0-'SE.ECTED MATTERS TO BE COMPLETED AFTER 1 i.. ^- ' ' Gm.ETION OF THE LOW POWER TE5T PRUERAM m-H s w, m. 8.1 LThe licensees shall perform ' secondary flow stability. tests prior to' y cachieving:100 percent power. The licenseeszshall submit andlobtain NRC fapprosaljof these: tests.. The licensees lshall provide at least 24-hours I.Li Lnot'if tcation to:IE' prior, to conducting such approved tests so that these ~ ~ w-a ~ itest!"may'be'witnes' sed by the NRC.. m .g '8.21Thejlicensees sha11-not operate-the reactor--at power levels above P-7 d f' ' (ar/ defined lin Table 3.3-1 of. Specification-3.3.1.1.of. Appendix A to

1. j this slisense))with fewer > than fbur reactor coolant. loops inl operation until.

'~ ? safety analyses 1for fewer than four loop operation have been submitted and- ~ bp approvalifor fewer $hsn four loop operation at power '1'evels above-P-7 has bun granted. by the Conunission by Amendment of this license. 18.3 - Prior.. to startup following the first regularly scheduled refueling outage, H the: licensees shall. imple!..ent the-fire prctection modifications as described I in the NRC ' Safety Evaluation Report, ' Sales Nuclear Generating Station, Unit Nos..liand.2 Fire Protection. Safety Evaluation Report"'(Appendix E + to Supplement No. '4 to the Salem Safety Evaluation Report. NUREG-0517). 8.4 Prior to the startup following theLfirst regularly. scheduled refueling outage, the licensees shall spec'ify the' details of the-inspection' program for guide. thimble tube wall wear. - 8.5 ' The'11censees shall take the following remedial actions, or alternative m - y actions. acceptable to the NRC. staff..with regards to the environmental , qualification; requirements appropriate to Class 1E equipment: cm 4 3~ , ;(1)..The' wide-range nsistance temperature detectors for the reactor ~ coolant; system shall.be qualified;for the radiation exposure for

40-year plant.. life and appropriate exposure contribution due to

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.a. ~ ' and acceptance by the NRC, each of:thase'~ detectors shall. be replaced ~ ^ j '. at each regularly scheduled ' refueling' outage. ~ m F p ,(2) ' Prior to completion of the'second scheduled refueling outago, ~ pressure-transmitters'anddifferentia1Lpressuretransmittetspm L Barton Lot I shall-have been replaced by. suitably qualified y.iice. d x~ ~

(3) - Prior to completion of the first-refueling outage, the Scotchcast No.391 resin-seals,'~used at the electrical connection interface on the j

'NAMCO limit switches, will be replaced with Conax Electric Conduction Seal. Assemblies.- 3 =, 8.6 Deleted. 5 a '8;7 Prior to exceeding five percent. power, the licensees shall plug the Row 1 tubes in the steam generators. j e l 8.8' At each of the first three regularly scheduled refueling outages, the iscenseesishall perform an ultrasonic inspection of the channelhead in the No. ' 21 -steam.. generator in a selected area. ( l E

8.9 Prior

to exceeding five percent power, the licensees shall install a reset = i alarm for the containment purge and pressure-vacuum relief valve reset j - circuitry.7 j s 8.10 prior to:startup.following the first regularly scheduled refueling outage, ] .J7 the' licensees shall. submit the confirmatory results of the containment f ,0 = 4 - sump mode 1Ltest program,[along with a descrip' tion of any sump modifications ej resulting from"the tests. 5 1 f 2 p

SALDI - UNIT. 2 -

,l - 8-2 AMEN 0 MENT NO. 3'- 3 y i l. ^ fr r r , =. _}}